Estimation of leak rates through a through-wall cracked pipes using Moody's critical flow model
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
To introduce Leak-Before-Break (LBB) concept into the piping design standard of the LWR pressure boundary piping, LBB research and verification test programs are actively conducted in many nuclear electricity generating countries. It is an important subject to evaluate the leak rate through a through-wall cracked pipes for the verification of LBB. At JAERI, a leak test program has started in 1987 in order to measure leak rates of coolant through cracks in 4- and 6-inch diameter pipes and through slit specimens. Using the Moody's critical flow model, a computer program to evaluate a leak rate through a through-wall cracked pipes has been developed in order to determine the crack angle of test pipes in the leak test. This report describes the Moody's critical flow model, the outline of the computer program and the results of preliminary calculations. (author)
Files
19078566.pdf
Files
(1.1 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- JAERI-M--88-039
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 19078566
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CRITICAL FLOW; FLOW RATE; LEAK TESTING; LEAKS; LOSS OF COOLANT; PIPES; PWR TYPE REACTORS; SATURATION; SUBCOOLING; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COOLING; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS